• Title of article

    An adaptive finite element approach for neutron transport equation

  • Author/Authors

    Abbassi، نويسنده , , M. and Zolfaghari، نويسنده , , A. and Minuchehr، نويسنده , , A. and Yousefi-Azari، نويسنده , , M.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2011
  • Pages
    12
  • From page
    2143
  • To page
    2154
  • Abstract
    In this paper, we develop an adaptive element refinement strategy that progressively refines the elements in appropriate regions of domain to solve even-parity Boltzmann transport equation. A posteriori error approach has been used for checking the approximation solutions for various sizes of elements. The local balance of neutrons in elements is utilized as an error assessment. To implement the adaptive approach a new neutron transport code FEMPT, finite element modeling of particle transport, for arbitrary geometry has been developed. This code is based on even-parity spherical harmonics and finite element method. A variational formulation is implemented for the even-parity neutron transport equation for the general case of anisotropic scattering and sources. High order spherical harmonic functions expansion for angle and finite element method in space is used as trial function. This code can be used to solve the multi-group neutron transport equation in highly complex X–Y geometries with arbitrary boundary condition. Due to powerful element generator tools of FEMPT, the description of desired and complicated 2D geometry becomes quite convenient. The numerical results show that the locally adaptive element refinement approach enhances the accuracy of solution in comparison with uniform meshing approach.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2011
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    1590898